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Merge remote-tracking branch 'upstream/develop' into hex_lattice
Conflicts: src/relaxng/geometry.rnc
This commit is contained in:
Sterling Harper
commit
1abb821bd6
25 changed files with 516 additions and 34 deletions
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@ -4,6 +4,292 @@
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State Point Binary File Specifications
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======================================
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-----------
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Revision 13
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-----------
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**integer(4) FILETYPE_STATEPOINT**
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Flags whether this file is a statepoint file or a particle restart file.
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**integer(4) REVISION_STATEPOINT**
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Revision of the binary state point file. Any time a change is made in the
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format of the state-point file, this integer is incremented.
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**integer(4) VERSION_MAJOR**
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Major version number for OpenMC
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**integer(4) VERSION_MINOR**
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Minor version number for OpenMC
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**integer(4) VERSION_RELEASE**
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Release version number for OpenMC
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**character(19) time_stamp**
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Date and time the state point was written.
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**character(255) path**
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Absolute path to directory containing input files.
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**integer(8) seed**
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Pseudo-random number generator seed.
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**integer(4) run_mode**
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run mode used. The modes are described in constants.F90.
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**integer(8) n_particles**
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Number of particles used per generation.
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**integer(4) current_batch**
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The number of batches already simulated.
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if (run_mode == MODE_EIGENVALUE)
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**integer(4) n_inactive**
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Number of inactive batches
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**integer(4) gen_per_batch**
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Number of generations per batch for criticality calculations
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*do i = 1, current_batch \* gen_per_batch*
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**real(8) k_generation(i)**
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k-effective for the i-th total generation
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*do i = 1, current_batch \* gen_per_batch*
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**real(8) entropy(i)**
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Shannon entropy for the i-th total generation
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**real(8) k_col_abs**
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Sum of product of collision/absorption estimates of k-effective
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**real(8) k_col_tra**
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Sum of product of collision/track-length estimates of k-effective
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**real(8) k_abs_tra**
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Sum of product of absorption/track-length estimates of k-effective
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**real(8) k_combined(2)**
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Mean and standard deviation of a combined estimate of k-effective
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**integer(4) cmfd_on**
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Flag that cmfd is on
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if (cmfd_on)
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**integer(4) cmfd % indices**
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Indices for cmfd mesh (i,j,k,g)
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**real(8) cmfd % k_cmfd(1:current_batch)**
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CMFD eigenvalues
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**real(8) cmfd % src(1:G,1:I,1:J,1:K)**
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CMFD fission source
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**real(8) cmfd % entropy(1:current_batch)**
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CMFD estimate of Shannon entropy
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**real(8) cmfd % balance(1:current_batch)**
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RMS of the residual neutron balance equation on CMFD mesh
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**real(8) cmfd % dom(1:current_batch)**
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CMFD estimate of dominance ratio
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**real(8) cmfd % scr_cmp(1:current_batch)**
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RMS comparison of difference between OpenMC and CMFD fission source
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**integer(4) n_meshes**
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Number of meshes in tallies.xml file
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*do i = 1, n_meshes*
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**integer(4) meshes(i) % id**
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Unique ID of mesh.
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**integer(4) meshes(i) % type**
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Type of mesh.
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**integer(4) meshes(i) % n_dimension**
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Number of dimensions for mesh (2 or 3).
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**integer(4) meshes(i) % dimension(:)**
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Number of mesh cells in each dimension.
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**real(8) meshes(i) % lower_left(:)**
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Coordinates of lower-left corner of mesh.
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**real(8) meshes(i) % upper_right(:)**
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Coordinates of upper-right corner of mesh.
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**real(8) meshes(i) % width(:)**
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Width of each mesh cell in each dimension.
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**integer(4) n_tallies**
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*do i = 1, n_tallies*
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**integer(4) tallies(i) % id**
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Unique ID of tally.
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**integer(4) tallies(i) % n_realizations**
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Number of realizations for the i-th tally.
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**integer(4) size(tallies(i) % scores, 1)**
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Total number of score bins for the i-th tally
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**integer(4) size(tallies(i) % scores, 2)**
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Total number of filter bins for the i-th tally
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**integer(4) tallies(i) % n_filters**
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*do j = 1, tallies(i) % n_filters*
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**integer(4) tallies(i) % filter(j) % type**
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Type of tally filter.
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**integer(4) tallies(i) % filter(j) % n_bins**
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Number of bins for filter.
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**integer(4)/real(8) tallies(i) % filter(j) % bins(:)**
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Value for each filter bin of this type.
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**integer(4) tallies(i) % n_nuclide_bins**
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Number of nuclide bins. If none are specified, this is just one.
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*do j = 1, tallies(i) % n_nuclide_bins*
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**integer(4) tallies(i) % nuclide_bins(j)**
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Values of specified nuclide bins
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**integer(4) tallies(i) % n_score_bins**
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Number of scoring bins.
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*do j = 1, tallies(i) % n_score_bins*
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**integer(4) tallies(i) % score_bins(j)**
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Values of specified scoring bins (e.g. SCORE_FLUX).
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*do j = 1, tallies(i) % n_score_bins*
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**integer(4) tallies(i) % scatt_order(j)**
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Scattering Order specified scoring bins.
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**integer(4) tallies(i) % n_score_bins**
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Number of scoring bins without accounting for those added by
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the scatter-pn command.
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**integer(4) source_present**
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Flag indicated if source bank is present in the file
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**integer(4) n_realizations**
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Number of realizations for global tallies.
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**integer(4) N_GLOBAL_TALLIES**
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Number of global tally scores
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*do i = 1, N_GLOBAL_TALLIES*
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**real(8) global_tallies(i) % sum**
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Accumulated sum for the i-th global tally
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**real(8) global_tallies(i) % sum_sq**
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Accumulated sum of squares for the i-th global tally
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**integer(4) tallies_on**
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Flag indicated if tallies are present in the file.
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if (tallies_on > 0)
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*do i = 1, n_tallies*
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*do k = 1, size(tallies(i) % scores, 2)*
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*do j = 1, size(tallies(i) % scores, 1)*
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**real(8) tallies(i) % scores(j,k) % sum**
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Accumulated sum for the j-th score and k-th filter of the
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i-th tally
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**real(8) tallies(i) % scores(j,k) % sum_sq**
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Accumulated sum of squares for the j-th score and k-th
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filter of the i-th tally
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if (run_mode == MODE_EIGENVALUE and source_present)
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*do i = 1, n_particles*
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**real(8) source_bank(i) % wgt**
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Weight of the i-th source particle
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**real(8) source_bank(i) % xyz(1:3)**
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Coordinates of the i-th source particle.
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**real(8) source_bank(i) % uvw(1:3)**
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Direction of the i-th source particle
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**real(8) source_bank(i) % E**
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Energy of the i-th source particle.
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-----------
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Revision 12
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-----------
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@ -757,7 +757,10 @@ Each ``<cell>`` element can have the following attributes or sub-elements:
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is on the negative side of surface 3 and the positive side of surface 5, the
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bounding surfaces would be given as "-3 5".
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*Default*: None
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.. note:: The surface attribute/element can be omitted to make a cell fill
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its entire universe.
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*Default*: No surfaces
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:rotation:
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If the cell is filled with a universe, this element specifies the angles in
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@ -1245,7 +1248,7 @@ implemented in openMC:
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``<plot>`` Element
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------------------
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Each plot must contain a combination of the following attributes or
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Each plot is specified by a combination of the following attributes or
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sub-elements:
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:id:
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@ -1266,6 +1269,18 @@ sub-elements:
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*Default*: ``cell``
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:level:
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Universe depth to plot at (optional). This parameter controls how many
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universe levels deep to pull cell and material ids from when setting plot
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colors. If a given location does not have as many levels as specified,
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colors will be taken from the lowest level at that location. For example, if
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``level`` is set to zero colors will be taken from top-level (universe zero)
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cells only. However, if ``level`` is set to 1 colors will be taken from
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cells in universes that fill top-level fill-cells, and from top-level cells
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that contain materials.
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*Default*: Whatever the deepest universe is in the model
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:origin:
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Specifies the (x,y,z) coordinate of the center of the plot. Should be three
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floats separated by spaces.
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